Abstract
The effective resonance integral for both fission and radiative capture is first calculated for differentsized rods of pure 239Pu at various temperatures in a graphite-moderated lattice. Then the contribution from 239Pu to the effective resonance integral of irradiated uranium rods in a graphite moderator is evaluated for the same rod sizes and temperatures, concentrations of 0·15 per cent and 0·2 per cent 239PU being considered in turn. The fuel temperature coefficient is estimated at both concentrations and compared to the temperature coefficient of the same rods at zero irradiation. The fractional change in fuel temperature coefficient due to 239Pu build-up is found to be small, in the absence of any allowance for neutron spectrum distortion in the region of the lowest 239Pu resonance, due to neutron thermalization.
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